ML18045A387

Forwards Request for Addl Info Re SEP Design Basis Events. Requests Response within 45 Days of Ltr Receipt

ML18045A387
Person / Time
Site:	Palisades
Issue date:	07/01/1980
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
TASK-15-01, TASK-15-02, TASK-15-07, TASK-15-1, TASK-15-2, TASK-15-7, TASK-RR NUDOCS 8007250693
Download: ML18045A387 (5)

Text

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Docket No. 50-255 NRR Reading

~ULY. 0 1 1980 ORB #5 Reading Mr. David P. Hoffman

.Nuclear Licensing Admfnistr~tor Consumers Power Company 212 West Michigan *-Avenue.

Jackson, Michigan _ 48201

Dear Mr. Hoffman:

DEisenhut TNovak RTedesco JHeJ temes RPruple

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• DCrutcht'i e 1 d TWambach

. HSmith RE: - SEP _DESIGN BASIS EVENTS REQUEST FOR_ ADDIJIONAL ~NFORMATIOrf We have.reviewed the-Palisades *Final *Safety-Analysis Report (FSAR) and

. "Plant:Transient Analys-is-of the Palisades Reactor for *operatfon*,a*f o

-2530 Mwt~' (XN-NF-77.;.18) and find that we require addf:tfonal information to continue our review~.The additional :information*needed*is identified f n the enclosure to thh 1 etter.

• _*Please respond wi thiri 45 dqys of your

-receipt of* this.1 etter.

Enclosure:

Reque-st for* Addi ti ona 1 *

• Information cc w/enclosure: *:

See page 2 *. * -

so' '07250 699 OFFICE~

c' ---sfoterely.---~

,.Ortginal signe~~~e1d.

Dennis M. crut.c Dennis -*M *. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D, C. 20555

• Docket No. 50-255*.

Mr.: David P. Hoffman Nuclear Licensing Administrator

.Consumers* Power Company

• 212 West Michigan Av~nue Jackson, Michigan 49201

Dear Mr. Hoffman:

July 19 1980 RE:

SEP DESIGN BASIS EVENTS REQUEST FOR ADDITION~L INFORMATION.

We have reviewed the Pa 1 i sades. Fi na.1 Safety Ana 1 ys is Report ( FSAR) and "Plant Transierit Analysis of the Palisades Reactor for Operation at 2530 Mwt" (XN-NF-77.;.18) and find that we require additional information*

to continue our review.

The additional information needed is identified in the enclosure to this letter. Please respond within 45 days of your receipt of this letter.

Enclosure:

Request fo~ Additiorial Information cc w/enclosure:

See page 2 Sincerely,

~c~~f~Jfil Oper~ting Reactors Branch #5 Division of Licensing

_ Mr. Cl avid P. Hoffman CC_ w/enclosure:-

M. I. Miller, Esquire*

-- Isham, Lincoln & Beale Suite 4200 One fir~t National Plaza Chicago, Illinois 60670 Mr. Paul A* Perry, Secretary

_ Consumers Power COIJl>any

.212 West Michigan Avenu~

Jacksbn, Michigan 49201 Judd L. Bacon, Esquire Consumers Power ColJl>any 212 West Michigan Avenue Jackson, Michigan -49201 Myr:-on M. Cherry~ Esquire *-

Suite 4501 One IBM Plaza Chicago, Illinois 60611 Ms. Mary P. Sinclair Great Lakes Energy Alliance 5711 Suminerset Ori ve Midland, Michigan 48640

_Kalamazoo Public Library 315 South Rose Street Kalamazoo, Michigan 49006 Township Supervisor Covert Township Route 1, Box 10 Van _Buren_ County, Michigan _ 49043 Office of the Governor (2)

Room 1 - Capitol Building Lansing, Michigan 48913 Director, Technical Assessment -

Division Office of Radiation Programs -

(AW-459)

U. s. En vi ronmenta 1 Protection Agency Crystal Mall #2 Arlington, Vi rgi ni a 20460.

• July 1, 1980

- u. S. Environmental Protection Agency Federal Activities Branch.

Region V Office ATTN:

EIS COORDINATOR 230 Sout_h Dearborn Street

• Chicago, Illi~ois 60604 Charles Bechhoefer, Esq., Chainnan Atomic Safety and Licensing Board Panel U. s. Nuclear Regulatory Comnission Washington, D. c. - 20555 Dr. George C. Anderson Department of Oceanography University of Washington Seattle, Washington 98195 Dr. M. Stanley Livingston 1005 Calle Largo Santa Fe, New Mexico 87501 Resident Inspector

- c/o u. s. NRC

_P. O._Box87-South Haven, Michigan 49090 Palisades Plant

-:ATTN:

Mr. J. G. Lewis

Plant Manager

• Covert, Michigan 49043 -

William J. Scanlon, Esquire 2034 Pauline Boulevard Ann Arbor, Michigan 48103

PALISADES

. REQUEST FOR ADDITIONAL INFORMATION

1.

FSAR and Amendment 17 analyses showed that a steam line break with loss of offsite power resulted in limited (<1%) fuel failures whereas the case with offsite power had no fuel failures.

The analysis presented in XN-NF-77-18 considered only the case with.offsite power.

Justify that this analysis is bounding for a steam line break with loss of offsite power, consider.ing the delay in SI initiation for diesel startup.

The turbine-generator coastdo'wn feature should be corisidered al so if it worsens the severity of the event by slowing the reactor. cool ant pump*

coastdown.

2.

Diesel-genera tor 1-2 powers 2 of 3 chargi n9 pumps and 2 of 3 HPSI pumps.

Thus, a s_ingl e failure of the diesel \\.\\Oul d result.in only 1 charging and.*

1 HPSI pump available for steam line break mitigaticin.

The analysis.

assumes 2 of 3 are av*ailable. Justify that a break with loss of offsite power and a single fa i1 ure of the di es el is bounded by the reference

• analysis.

3. *In *xN-NF-77-lB, Section 3.4.2 (Increase in feedwater. flow), the analysis*

• .considers an event from 50% flow with EOC kinetics parameters.

Justify.

~hat this event is more limiting than:*

a. a transient initiated from full power, EOC kinetics, due to the*

potential overpower ~ondition

b.

a transient with BOC kinetics, manual control, which could ca*use a pressure decrease and thus a cl os.er approach to DNB, even though.

power is not increasing.

J

... ~. '..

. 4.

For the locked rotor event, what are the consequences if a turbine trip and coincident loss of offsite power are assumed, so that the remaining reactor cool~nt pumps coastdown.

'5. For both the excess load increase (athot'standby)'and the steam line

6.

break events, HPSI flow is needed to mitigate the consequences.

Please explain how the time at which the fl6w reaches the tore is derived, since in the first event, the flow arrives 32 seconds after SI, whereas for the ste~m line break, it arrives only 18 seconds aft~r SI:

The Reduction in feedwater enthalpy.event (3.4.l) was analyzed with BOC coefficients to 11maximi ze the depressuri zation and thus obtain a conserv-

. ative predictio~ of DNB.

11 However, the figures show that at 8 seconds, when the MDNBR occurs (MDNBR~l.75, ~hich is. the steady*state value),

pressure has actually increased slightly. *Please justify why a case at EOC, where power would increase during the transient, is not more limiting.

7.

A steam line break upstream of the main steam line i~olation valve (MSIV) in*

one )ine combined with a failure to close 6f the MSIV in the unaffected line.*

could al~ow both generator~ to blowdown~ The non-ruptured generator blows down through the check valve (MSIV) of the ruptured lin~. This scenario has not

.been analyzed for Palisades.

. Justification should be provided that such a failure is not credible, or an analysis $hould be done, considering locations both inside and outside contain-ment.

The plant capacity for controlled decay heat removal under these conditions shbuld also be addressed.